Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 61, NRC Generic Aging Lessons Learned (GALL) Report (Vol. 2, Rev. 1, at II A.1 Through 5), Portions Discussing Concrete Containment Structures| ML072780503 |
| Person / Time |
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| Site: |
Oyster Creek |
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| Issue date: |
09/30/2005 |
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| From: |
AmerGen Energy Co |
|---|
| To: |
NRC/SECY |
|---|
| SECY RAS |
| References |
|---|
| 50-219-LR, AmerGen-Applicant-61, RAS 14275 |
| Download: ML072780503 (6) |
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Category:Legal-Exhibit
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Official Exhibit - STP000090-00-BD01 - Safety Evaluation by NRR, Proposed Transfer of Oyster Creek Nuclear Generating Station Operating License from Jersey Central Power & Light Company and Gpu Nuclear, Inc. to Amergen Energy Company, LLC,
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2008/04/03-Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH_24, NRC, Notification of Information in the Matter of Oyster Creek Nuclear Generating Station License Renewal Application (April 3, 2008)
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Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit a, List of Exhibits
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Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit a, Staff Exhibit List
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Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 63, Note: Deliberately Omitted, Provided as Amergen Exhibit 7
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Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 E, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region
ML0727805712007-09-24024 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 C, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region
ML0727805752007-09-24024 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 D, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region
ML0727805552007-09-24024 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 a, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region
ML0727805642007-09-24024 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 B, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region
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Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 5, Exelon Nuclear, Calculation C-1302-187-E310-041 Revision 0: Statistical Analysis of Drywell Vessel Sandbed Thickness... Note: Intentionally Omitted.
ML0728303182007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit D, Curriculum Vitae of Rudolf H. Hausler
ML0728500642007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 51, Sketches Showing Ultrasonic and Echo to Echo Techniques, and Explanations of Sketches (OCLR00026641)
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Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 23, Amergen, Disclosed Document Relating to Drywell Leakage (Ref. # OCLR00013354)
ML0728501062007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 59, Deliberately Omitted, Submitted by Amergen as Applicant Exhibit 39
ML0728303162007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 9, Schematic Drawing Showing Detail of the Reactor Cavity Section, Detail a
ML0727805002007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 60, L. Bertolini, Et Al., Corrosion of Steel in Concrete - Prevention, Diagnosis, Repair, Wiley - Vch, Weinheim, Germany, 2004, Selections Describing Corrosion Rates.
ML0727705942007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 7, Schematic Drawing Showing Detail of the Lower Drywell/Sand Bed Region
ML0727705452007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 25, Table Showing the Location, Mean Thickness (by Date), and the 95% Confidence Interval of the Internal UT Grid Data for the Sand Bed Region, 1992, 1994, 1996, 2006.
ML0728303252007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 2, Partial Cross Section of Drywell and Torus
ML0727705872007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 5, Schematic Drawing of the Drywell Shell Exterior
ML0727805522007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 48, ASME Code Section XI, Article IWE: Inservice Inspection, Repair, and Replacement of Class Mc Pressure-Retaining Components
ML0728500402007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 37, Background and Statement of Facts
ML0727805312007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 43, Figure Showing Bay 19 UT Thickness Measurements and the Significant Difference Between Two Types of Statistical Confidence Limits
ML0727805282007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 44, Scaled Maps of Internal and External UT Thickness Measurements for Bays 1, 13, 17, and 19
ML0728500342007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 33, Exelon Nuclear, Calculation C-13-2=198=532-=-24 Rev/ 2 P/C/ Drywell Ext. UT Eavluation in Sand Bed - Note: Intentionally Omitted, Submitted by Amergen.
ML0728304812007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit C, Hausler Rebuttal Affidavit - Corrected Numbering. No Other Changes to Document
ML0728500322007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 31, Amergen, Calculation Sheet C-1302-187-5300-011, Note: Intentionally Omitted, Submitted by Amergen at Applicant Exh. 23
ML0727705802007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit a, Amergen'S List of Exhibits
ML0727706222007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 11, Drawings of the 0.536 Local Buckling Acceptance Criterion Tray (Front and Isometric Views)
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Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 36, Curriculum Vitae of Dr. Har Mehta (Duplicative of Witness Curriculum Vitae That Forms Part of Exhibit D)
ML0727705992007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 8, Schematic Drawing Showing Detail of the Drywell to the Reactor Cavity Seal Detail, Detail B
ML0727705912007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 6, Schematic Drawing Showing Top View of the Ten Bays in the Sand Bed Region
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Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit 4, Exelon Procedure TQ-AA-122, Rev. 3; Qualification and Certification of Nondestructive (NDE) Personnel
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Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 4, Schematic Drawing of the Cross-Section of the Drywell Shell (Embedded Into a Concrete Pedestal Atop the Reactor Building Concrete Foundation)
ML0728303312007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 4, Exelon Nuclear, Calculation C-1302-187-5320-024 Revision 1: O.C. Drywell Ext. UT Evaluation in Sandbed - Note: Intentionally Omitted.
ML0728508272007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit D, Professional Qualifications of Staff Witnesses, This Exhibit Contains All Statements of Professional Qualifications That Are Also Included in Staff Exhibits B.
ML0727805212007-09-20020 September 2007
Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 35, Devoe Coatings Data Sheets for the Epoxy Coating System Installed in the OCNGS Sand Bed Region: Devoe Pre-Prime 167 and Devran 184: 100% Solids...
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Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 8, Amergen, Passport 00546049 07 (AR A2152754 E09): Water Found in Drywell Trench 5 - UT Data Evaluation - Note: Intentionally Omitted.
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Oyster Creek - Staff Exhibit 4 to the NRC Staff Response to Rebuttal Presentations
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Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit C.1, NRC Staff Sur-Rebuttal of Hansraj G. Ashar, Dr. James Davis, Dr. Mark Hartzman, Timothy L. O'Hara, and Arthur D. Salomon
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Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit C.1, Sur-Rebuttal Testimony
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Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit C1, Prefiled Sur-Rebuttal Written Testimony of Dr. Rudolf H. Hausler Regarding Citizens' Drywell Contention
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Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 54, OCNGS Work Order No. R2104033: Inspect Poly Bottles for Presence of Water, 8-28-2007 Inspection Results
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Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit C, Rebuttal Testimony
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Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit C, NRC Staff Rebuttal Testimony of Hansraj G. Ashar, Dr. James Davis, Dr. Mark Hartzman, Timothy L. O'Hara and Arthur D. Salomon and Answer to Board Questions
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Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 39, Memorandum from Dr. Rudolf Hausler, Subject: Further Discussion of the Nature of the Corroded Surfaces and the Residual Wall Thickness of the Oyster Creek Dry Well
ML0728500422007-08-16016 August 2007
Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 38, Memorandum from Dr. Rudolf Hausler, Subject: Response to the Questions About Statistics
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Amergen'S Pre-filed Direct Testimony Exhibits - Volume 1 of 2: Exhibits 1 - 19
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Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit B, Initial Testimony
2013-07-01
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Text
RA S / L/ t7j5 APPLICANT'S EXHIBIT 61 NUREG-1801, Vol. 2, Rev. 1 Generc Lsson Agng US. NUCLEAR FEVOL COMMISSION In~M~rofA1At~~ v~EPIco-, UX.-
Generic Aging Lessons *92-lZ- Official Exhibit No. 62 k Do"tst NO.-
Learned. (GALL) Report OFFERED by* 4ý jnsee Intervenor NR St4ff Other IOENTIFIED on I L - 0*Nitness/Panel Acton Taken: DM"OTHDRAWN JECTED Reporter/Clerk (9V Tabulation of Results Manuscript Completed: September 2005 Date Published: September 2005 DOCKETED USNRC October 1, 2007 (10:45am)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
. . p. R E . . .
4 ~ CO
Al. CONCRETE CONTAINMENTS (REINFORCED AND PRESTRESSED)
Systems, Structures, and Components This section addresses the elements of pressurized water reactor (PWR) concrete containment structures. Concrete containment structures are divided into three elements: concrete, steel, and prestressing system.
System Interfaces Functional interfaces include the primary containment heating and ventilation.system (VII.F3),
containment isolation system (V.C). and containment spray system (V.A). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B1) and feedwater system (VIII.Dl), or is supported by the containment structure, such as the polar crane (VII.B). The containment structure basemat typically provides support to the nuclear steam supply system (NSSS) components and containment internal structures.
September 2005 II1A1-1 NUREG-1801, Rev. 1
z II CONTAINMENT STRUCTURES C
Al Concrete Containments (Reinforced and Prestressed) m 0
00 Structure Further C Item Link and/or Material Environment Agingism Aging Management Program (AMP)
Mechanism Evaluation Component (D
I1.A1-1 II.A1.1-h Concrete: Concrete Air - indoor Reduction of Plant-specific aging management Yes, if uncontrolled or strength and program temperature (C-08) Dome; wall; air - outdoor modulus/ elevated limits are basemat; ring temperature The implementation of 10 CFR 50.55a exceeded girder; (>150'F general; and ASME Section XI, Subsection IWL buttresses >200'F local) would not be able to identify the reductic.,i of strength and modulus of elasticity due to elevated temperature.
Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted. Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150'F except for local areas, such as around penetrations, which are not allowed to exceed 200'F. If significant equipment loads are supported by concrete at temperatures exceeding 150'F, an evaluation of the ability to withstand the postulated design loads is to be made.
Higher temperatures than given above may be allowed in the concrete if tests and/or calculations are provided to C',
CD evaluate the reduction in strength and
'R CD this reduction is applied to the design 27 allowables.
CD a __________ u U I. L NJ C
C-,
(n CD II CONTAINMENT STRUCTURES
'R CD Al Concrete Containments (Reinforced and Prestressed) 3 Structure Further CD Item Link and/or ,ging Management Program (AMP) Evaluation CD Component I .
II.A1-2 II.Al. 1-a Concrete: Chapter XI.S2, "ASME Section XI, Yes, for (spalling, scaling) Subsection IWL" inaccessible (C-01) Dome; wall; and cracking/ areas of plants basemat; ring freeze-thaw Accessible areas: located in girders; Inspections performed in accordance moderate to buttresses with IWL will indicate the presence of severe loss of material (spalling, scaling) and weathering surface cracking due to freeze-thaw. conditions Inaccessible Areas:
Evaluation is needed for plants that are located in moderate to severe weathering conditions. (weathering index
>100 day-inch/yr) (NUREG-1557).
Documented evidence confirms that where the existing concrete had air content of 3% to 6%, subsequent inspection did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation.
The weathering index for the continental L £ US is shown in ASTM C33-90, Fig. 1.
a u .1.
z m
0o Cý CD
z 11 CONTAINMENT STRUCTURES C:
Al Concrete Containments (Reinforced and Prestressed) m 00 Structure Aging Effect/ Further Item . Link and/or Material Environment Mechanism Aging Managemern Program (AMP) Evaluation Component CD Yes, if II.A1-3 II.A1.1-d Concrete:. Concrete Any Cracking due to Chapter XI.S2, "ASME Section XI, expansion/ Subsection IWL" concrete was (C-04) Dome; wall; reaction with not basemat; ring aggregates Accessible /..,-eas: constructed as girders; Inspections performed in accordance stated for buttresses with IWL will indicate the presence of inaccessible surface cracking due to reaction with areas aggregates.
Inaccessible Areas:
As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R.Therefore, if these conditions are satisfied, aging management is not
_necessary.
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CD CD 3
0 (n1
II CONTAINMENT STRUCTURES Al Concrete Containments (Reinforced and Prestressed)
Structure Aging Effect/ Further Item Link and/or Material Environment Mechanism Aging Management Program (AMP) Evaluation Component II.A1-4 II.A1.1-c Concrete: Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, Yes, plant-water/soil or air porosity and Subsection IWL". specific if (C-03) Dome; wall; indoor permeability, environment is basemat; ring uncontrolled or cracking, loss of Accessible Areas: aggressive girders; air-outdoor material (spalling, Inspections performed in accordance buttresses scaling)/ with IWL will indicate the presence of aggressive increase in porosity and permeability, chemical attack surface cracking, or loss of material (spalling, scaling) due to aggressive chemical attack.
Inaccessible Areas:
For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.
For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.